| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 5.599 (b) | 6.321 (b) | 1.129 | − | 3.789 (b) | 5.396 (b) |
| 2 | (n,elastic) | 5.594 (b) | 6.315 (b) | 1.129 | − | 2.049 (b) | 4.879 (b) |
| 4 | (n,inelastic) | ( E-thr = 1.857 MeV ) | 742.0 (mb) | 514.3 (mb) | |||
| 16 | (n,2n) | ( E-thr = 11.24 MeV ) | 980.6 (mb) | 197.3 (μb) | |||
| 22 | (n,na) | ( E-thr = 8.006 MeV ) | 0.000 (b) | 2.448 (nb) | |||
| 28 | (n,np) | ( E-thr = 10.73 MeV ) | 80.97 (μb) | 123.1 (nb) | |||
| 102 | (n,γ) | 5.801 (mb) | 5.804 (mb) | 1.000 | 31.28 (mb) | 399.5 (μb) | 1.943 (mb) |
| 103 | (n,p) | ( E-thr = 4.582 MeV ) | 14.65 (mb) | 7.180 (μb) | |||
| 104 | (n,d) | ( E-thr = 8.485 MeV ) | 346.7 (μb) | 112.2 (nb) | |||
| 105 | (n,t) | ( E-thr = 12.19 MeV ) | 0.000 (b) | 744.2e-12 (b) | |||
| 106 | (n,He-3) | ( E-thr = 11.65 MeV ) | 0.000 (b) | 585.4e-18 (b) | |||
| 107 | (n,a) | ( E-thr = 804.2 keV ) | 2.048 (mb) | 740.3 (nb) | |||
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These cross sections are calculated from JENDL-4.0 at 300K.
The background color of each cell noted a cross section means the order of the cross-section value.
The unit of cross section, (b), means barns, and SI prefixes are used as following.
(kb) → 103(b), (mb) → 10−3(b),
(μb) → 10−6(b), (nb) → 10−9(b).
MT is a number that defines a reaction type. For the relation between MT and reaction type, please see here or refer to the manual of ENDF formats.
Maxwellian Average :
where T denotes the temperature, and kB the Boltzmann constant.
The upper and lower limits of integration, EL and EU
are set to 10−5 eV and 10 eV, respectively.
Resonance Integral :
with EL = 0.5 eV and EU = 10 MeV.
U-235 Thermal Fission-Neutron Spectrum Average (Fiss. Spec. Average) :
with EL = 10−5 eV and EU = 20 MeV.
The parameters a and b are 0.988 MeV and 2.249 MeV−1, respectively.
Westcott g-factor :
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